Transcript Nuclear data at n_TOF for fundamental science and technological applications Enrique M.

Nuclear data at n_TOF for fundamental
science and technological applications
Enrique M. González Romero
CIEMAT, on behalf of the n_TOF Collaboration
Workshop on Applications of High Intensity Proton Accelerators
Fermilab
20-X-2009
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
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INTRODUCTION
New problems, New concepts, New materials or New procedures will need
dedicated experimental validation.
The first step should be done in basic experiments at specialized
experimental reactors that allow to identify and separate the different
Phys/Chem phenomena: E.g. Monitoring reactivity in ADS
Today there are many problems where it is possible to perform high precision
computer simulation. This applies in particular to neutronics, shielding and
other core physics problems when nuclear data is accurate enough.
In this way, simulations can optimize and enhance the value of those
experiments and even reduce the number of experiments needed
Today, high precision simulation is often cheaper and faster than the actual
experiments, and normally provides much more details of the process – But it
needs accurate basic (nuclear) data and always needs some experimental
validation of its absolute accuracy.
The important role of simulation and basic data is in the SRA of SNETP
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
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Some possible (new) roles of high precision simulations
include:
Optimization of experiment (at any scale) planning
- Significant results will be obtained?
- Experimental setup/devices are appropriated
- Progress vs state of the art / Conclusive results ?
Exploitation (substitution) of experim. results and operational experience
- Understanding available data
- Interpolation of experimental results
- Exploration of interest for difficult/expensive possibilities before exper.
- Estimation of results for presently unreachable conditions
Guiding decision making
- Choices in early phases of the projects
- Choices with limited (expensive) experimental information
E.g. SNETP Choices of alternative systems in 2012
Education and Training
Accurate nuclear data an selected basic (neutronic) experiments are key pieces to
reduce uncertainties and increase confidence for safety and design
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
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- n- induced fission (energy + wastes)
- neutron capture
(activation + breeding)
- elastic and inelastic neutron scattering
- radioactive decay
- (n,xn), (n, charged particle), …
Main reactions in a
nuclear reactor or
transmutation device
(n, X+charged part.)
b+
b-
fission
Standard reactor
1500 isotopes
ADS with spallation
3000 isotopes
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
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Rate   n  ( E ) ( E ) dE
 (E )
238U
Capture
235U Fission
- n- induced fission
- neutron capture
- elastic and inelastic neutron scattering
Thermalization, Moderation
1meV
1eV
1keV
1MeV
Resonances (absorption, elastic, inelastic,…)
 (E )
Pressurized
Water cooled
Reactor
 (E )
Lead (Pb/Bi)
cooled
Fast ADS
1keV
1MeV
1meV
1eV
1keV
1MeV
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
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Present in nuclear wastes
Medium Half-Life (<100 años)
Short Half-Life (< 30 dias)
High A actinides
Thermal and Fast Fission
Fast Fissión
Low Fission Cross Section
TRU Transmutation Scheme
Fast Spectrum
Fast Spectrum Transmutation Scheme
Av. Flux Intensity (n/cm2/s)
3,00E+15
Second
Hour
Day
Year
1 Time Unit
3600 31570560
86400
3E+07
Cm242
Cm243
Cm244
Cm245
Cm246
a / SF
a / EC/ SF
a / SF
a / SF
a / SF
a
100 / 6.2E-6
9 9 . 7 / 0 . 2 9 / 5 . 3 E- 9
100 / 1.35E-4
100 / 6.1E-7
100 / 3E-2
100
0,446
29,068
18,080
8490,695
4724,813
18,130
2,798
6,257
2,922
16,459
64,7%
8,0%
65,2%
11,4%
44,6%
Am241
Am242
Am243
Am244
a / SF
b- / EC
IT / a / SF
a / SF
b- / EC
100 / 3.77E-10
82.7 / 17.3
9 9 . 5 / 0 . 4 6 / 1 E- 3
100 / 3.7E-9
100 / 4E-2
Am242m
432,225
0,002
140,846
3,652
7361,922
17,792
1,844
4,892
44% : 44%
13,1%
8,4%
87,0%
Pu239
Pu240
Pu241
Pu242
Pu243
a / SF
a / SF
a / SF
b- / a
a / SF
b-
100 / 1.9E-7
100 / 3.1E-10
100 / 5.7E-6
100 / 2.45E-3
100 / 5.5E-4
100
87,644
24083,608
6556,805
14,334
372891,707
0,001
4,220
3,477
9,033
2,688
11,354
6,775
37,5%
19,4%
54,8%
14,2%
61,1%
30,6%
Np238
Np239
a / SF
b-
b-
100 / 2E-12
100
0,006
4,332
15,928
Pu239
a / SF
100
2137656,095
0,006
U239 <- n+U238
13,1%
E. Gonzalez: Nuclear
data at n_TOF for fundamental science and industrial
81,5%
15582935,494
0,001
Pu238
Np237
Cm247
Symbol & Mass
Decay modes
100 / 3.1E-10 Branching ratios
24083,608 Half-Life
Ln(2)/(f)
3,477 Absorption-Half-Life
19,4% (n,g)/absoption
applications (AHIPA09 - Fermilab)
6
Steps to identify data needs
• Identify present uncetainties
• Identify relevant basic data:
Isotopes, reactions, energy range
Required precision for the data
Priorities for different data
Estimate Experimental feasibility and
timely availability of experim. facilities
End Users Group
Designers, Builders and
Utilities.
Strategic choices.
Simulation tools
Internat. Coop/ NEA / IAEA
Uncertainty evaluation
(M.C., Linear Deriv.)
Sensitivity analysis
Global optimization and
evaluation of required
measurements /
evaluations and needed
accuracies
Need for complete and
reliable uncertainties
and correlations.
• All technologies can profit from better data:
Gen II, Gen III(+), Gen IV and P&T
• Industrial, Exp. Reactors and Fuel Cycle
• Identify relevant parameters and target
precision and priorities on those parameters
Coordinate needs from different technologies/fuel cycle
Reevaluation of priorities and accuracies
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
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Fuel
Fabrication
(D<0.5%)
Reactors: (D<0.5%)
Performance: Reaction rates,
Power distribution, Flux, Energy
Spectrum
Safety: Criticality, Feedbacks,
Reactivity coeffs, Damage, Shielding
Waste: Isotopic evolution, activation
Nuclear
Power Plant
Interim
Storage
SPENT FUEL
Storage, Reprocessing and
Fabrication plants: (D<5%-10%)
Reprocessing
Plant
High Level Wastes
High Level
Liquid Wastes
Advanced
Aqueous
Partitioning
Minor (MA)
Actinides
Fabrication
of new fuels
and Targets
Storage, Reprocessing and
Fabrication plants: (D<5%-10%)
Fission (FP)
Products
HLW
High
Level
Wastes
Deep Geological
Repository for
High Level Wastes
Pyrochemical Partitioning
Isotopic composition !!!
Radioactivity, Neutron emissions,
Decay Heat,
Proliferation interest
ADS Transmuter
Isotopic composition !!!
Radioactivity, Neutron emissions,
Decay Heat,
Proliferation interest
Radiotoxicity and Dose to Public and
Environment
Effective capacity
Standard
Advanced Reprocessing
E. Gonzalez:Open
Nuclear data
at n_TOF for
fundamental
science and industrial applications (AHIPA09 - Fermilab)
Cycle
Reprocessing
(Partitioning
and Transmutation)
8
Sensitivity analysis – ADS for Transmutation
keff
(from G. Aliberti et al.,
NSE 146, 13–50, 2004)
a) Upper limit of the group
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
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NEA/WPEC-26.
One possible optimization for
target accuracy for innovative
systems using recent
covariance data evaluations
(BOLNA).
M. Salvatores and R.
Jacqmin (Eds),
NEA/WPEC-26.
ISBN 978-92-64-99053-1
Similar tables for each
present or proposed future
reactor
Still serious dependence on
the reactor and fuel models
and on the transmutation
model (homogeneous) can
slightly modify the target
accuracy and details on the
priority order
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
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Important isotopes for Transmutation Fuel Cycles: The multirecycling point of view
Report of the
Numerical results
from the Evaluation of
the nuclear data
sensitivities, Priority
list and table of
required accuracies
for nuclear data. E.
Gonzalez-Romero
(Ed), NUDATRA
Deliverable D5.11
from IP-Eurotrans
T= Transmutation efficiency
DH= Decay Heat load
N = Neutron emission
R = Radiotoxicity
Isotopes
234
U
U
236
U
237
Np
238
Pu
239
Pu
240
Pu
241
Pu
242
Pu
241
Am
242m
Am
243
Am
242
Cm
243
Cm
244
Cm
245
Cm
246
Cm
247
Cm
248
Cm
250
Cf
252
Cf
235
Uncertainty
in
abundance %
Burnup (GWd/t)
150
500
4.6
16.1
13.1
18.4
1.8
7.6
6.3
23.7
4.3
10.8
4.6
12.9
2.0
7.0
8.2
14.7
2.1
7.9
7.2
20.7
12.8
28.6
6.6
15.6
10.7
7.7
23.3
32.6
6.0
13.3
13.3
18.8
7.5
21.7
15.4
27.2
6.4
19.8
31.9
28.9
52.4
46.1
the
Important for:
800
32.4
15.5
12.6
28.1
19.3
17.8
14.4
17.0
16.2
26.0
34.4
20.2
15.6
35.7
19.1
16.3
31.5
31.6
31.4
36.9
48.9
T
T
T
T
T
T
T
T
T
T
T
T
T
DH
T
T
T
T
DH
DH
DH
DH
DH
DH
R
R
R
DH
DH
R
R
DH
DH
R
N
R
R
R
N
N
N
N
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
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Identifying and setting priorities of Nuclear data for
applications: An international endeavor
• Applications set the problems to be analyzed and the required accuracies for the
simulation.
• Detailed uncertainty and covariance propagation to evaluate the accuracy.
• Sensitivity analysis identify the relevance of each data for each
isotope/reaction/energy on the most significant parameters
• Linear Optimization with expert assessment of “cost” (experimental difficulties) to set
priorities
Efforts coordinated by dedicated expert groups of NEA/OECD, IAEA, and
dedicated EU framework programs
EU support and demand for nuclear data measurements:
• Clear and repeated demand from the Nuclear Waste community, Sustainability of
Nuclear Energy (Resources, Safety, Waste) by EU Framework Program calls:
- FP5: nTOF_ND_ADS (start of n_TOF facility at CERN)
- FP6: NUDATRA (inside EUROTRANS),
- FP6: EFNUDAT (Transnat. Access) + CANDIDE (Roadmap for ND)
- FP7: ANDES proposal to WP2009
• Collaboration with other measurements at USA, Japan, Russia.
One EU call on Nuclear Data for each FP (FP5-FP7),
n_TOF measurements in all of them
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
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n_TOF Collaboration
A group of 23 institutions from 14 countries (today)
(A, D, Ch, Cz, E, F, I, Gr, P, Po, Ro, India, Jp, Ru)
working together from 1998 to measure
Precision Neutron cross sections for
Nuclear Astrophysics
Sustainable Nuclear Technologies
Basics Physics
using the neutron time of flight facility at CERN
A nice social experiment of joining communities that discovered
that most cross section needs and interesting measurements were
common and that now share resources (shifts, detectors,
analysis…) and results for each single measurement at CERN.
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
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2000: A
view of n_TOF
n_TOF 185 m
flight path
Booster
1.4 GeV
Pb Spallation
Target
Neutron Beam
10o prod. angle
Proton Beam
20GeV/c
7x1012 ppp
Linac
50 MeV
PS 20GeV
2001: The real world
from inside
 n_TOF commissioned
in 2001-2002
www.cern.ch/n_TOF
2
10
1
10
0
GELINA
232
Th (0.0016 at/b)
208
Pb
10
Concept
by C.Rubbia
CERN/ET/Int.
Note 97-19
2001-2004
Proposal
submitted
n-TOF
232
Th (0.0041 at/b)
208
Pb
-1
10
100
1000 10000 100000
Neutron Energy / eV
Phase I
Isotopes
Capture: 25
Fission: 11
Papers: 21
Proc.: 51
Doc: 150
Problem
Investigation
Phase II
2010
Construction
started
10
2004-2007
Response (counts / ns)
1999
CERN/LHC/9802+Add
2009
Feasibility
Aug 1998
1997
New Target
construction
Commissioning
May 2009
2008
Commissioning
TARC
experiment
May 1998
1995-1997
2000
n_TOF timeline
Upgrades:
Borated-H2O
Second Line
Class-A
n_TOF beam characteristics
•
•
•
•
•
•
2nd collimator f=1.8 cm (capture mode)
Wide energy range
High instantaneous n- flux
High resolution
Low ambient background
Low repetition frequency
Favorable duty cycle for
radioactive samples.
Capture (0.1eV-1MeV)
Fission (0.1 eV-20MeV)
Spallation (1keV-200MeV)
One of the best worldwide facilities for radioactive samples:
Complementary to GELINA (EU JRC-IRMM@Geel, Belgium)
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
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n_TOF: Advanced DAQ and detectors
+ Precision simulations (Geant4, MCNPX, Fluka): Utilization and Validation
Low n-sensitivity capture detectors
First FADC DAQ for T.o.F facilities
Total Absorption Segmented Calorimeter
Fission detector reconstructing F.F. trajectories
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
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Capture
151Sm
204,206,207,208Pb, 209Bi
232Th
24,25,26Mg
90,91,92,94,96Zr, 93Zr
n_TOF experiments
2000-2004 measurements
Sensitivity analysis
NSE 146, 13–50 (2004))
NEA/WPEC-26 (2008)
139La
186,187,188Os
233,234U
NUDATRA Deliverable D5.11 of IP-Eurotrans (2009)
Other types of reactor & cycles (Th-U, PWR)
237Np,240Pu,243Am
Fission
233,234,235,236,238U
232Th
Challenge for the first n_TOF campaign:
- To improve the quality of previous measurements
- Demonstrate feasibility of challenging isotopes
209Bi
237Np
241,243Am, 245Cm
All data first published then stored
in the EXFOR database
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 The
- Fermilab)
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n_TOF Collaboration
n_TOF measurements are designed to obtain the maximum
information for basic nuclear physics
• Nuclear structure models
- Improving the accuracy and statistical information from resolved resonances
(RR)
Extending the RR region
Level densities and criteria for the estimation of missed resonances
- Photon Strength functions from the TAC
- Direct vs. compound nuclei mechanism
- Measurements in closed-shell nuclei and light nuclei (Pb, Mg,…)
• Fission: towards a better understanding of the process
- High resolution measurements over large energy ranges in the same setup
- FF kinetic energy and angular distributions determination
- Fissile (233U, 235U, 245Cm) and Fissionable isotopes (234U, 232Th, …)
- Sub-threshold, direct and multiple chance fission
- Fine structures in the fission barriers (outer fission barrier and hyperdeformation of the fission potential)
• Basic reactions
- n-n scattering by 2H(n,np)n
- (n, l.c.p.) reactions (l.c.p. = light charged particles like p, a, 3H, Li,…)
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
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High resolution low backgr. of radioactive samples: 232Th by C6D6
High peak n flux
intensity reduce the
radioactive
background
+ high resolution
-> larger RRR +
Small resonances
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
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High resolution low backgr. of radioactive samples: 237Np TAC
n_TOF
capture
+
GELINA
transmission
=
One of the
best measur.
made at
Europe.
C. Guerrero et al. (n_TOF Collaboration), Proc. Int. Conf. Nuc. Data for Sci. and Tech. 2007, Nice.
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
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High resolution low capture cross section samples: C6D6 + TAC
204Pb
Fitting of resonance parameter in progress!
Impurities
In, Sb
first known
Mg resonance
at 20 keV
206Pb
M.Heil (FZK), Nuclei in the Cosmos IX,
Geneva 2005
C.Domingo-Pardo et al. (n_TOF
Collaboration), Phys. Rev. C 74/75, 2006/7
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
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High resolution and large energy range accurate fission data
235U:
High
accuracy
differences
245Cm:
poor previous
experimental results
233U:
n_TOF vs
ENDF BVII
238U/235U:
both isotopes
are fission standards up
to 200 MeV.
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
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High resolution and large energy range accurate fission data
Fine structures in the fission
barriers (outer fission barrier
and hyper-deformation of
the fission potential)
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
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n_TOF_ph2 experiments
Current program
Reaching required accuracy indicated by the
sensitivity analysis : (5-10%) M.A. and (2%5%) for main isotopes.
Capture
Stable Isotopes:
Mo,Bi: Materials for fuel matrix (Mo) and coolant (Bi)
Fe, Ni, Zn, 79Se: Structural materials
234,236,238U, 231Pa: Th/U fuel cycle
239,240,242Pu,241,243Am, 245Cm: transmutation of minor actinides
Fission
231Pa,234,235,236,238U
: Safety and sustainability of nuclear energy
241Pu,241,243Am, 244Cm, 245Cm : transmutation of minor actinides
234U: study of vibrational resonances below the barrier
Other
n-n scattering by 2H(n,np)n
Sensitivity
analysis
NEA/WPEC-26
(2008)
NUDATRA
Deliverable D5.11
of IP-Eurotrans
(2009)
Other types of
reactor & cycles
(Th-U, PWR)
(n, lcp) (lcp = light charged particles like p, a, 3H, Li,…)
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
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n_TOF_ph2 experiments
Main upgrades from n_TOF
• New target, target cooling station and ventilation system (improving safety and
reliability)
• New fission detectors to measure more physical magnitudes (angle, kinetic
energy)
• New capture samples design for the calorimeter with lower beam scattered
background
• The possibility to have independent moderator and cooling circuits:
• Moderation by borated water to reduce in-beam g background.
Further upgrades ahead:
• convert EAR1 to Class A/B Rad. Laboratory
• Building a new short flight path and the associated experimental area EAR2
(also expected to be Class A Rad. Laboratory )
Most measurements proposed before can be done with the facility as it is (3 first
upgrades), however some fission targets are conditioned by R.P. rules and will
require to upgrade the Experimental Area to a Class A/B Rad. Laboratory.
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
27
The 2008 Upgrade
- Design and build of new
spallation target and pit lay-out
- New cooling station
- New ventilation system
- Additional shielding and radioprotection actions
- Updated detectors and DAQ
New spallation target
The next frontier: n_TOF @ EAR2
Present in nuclear wastes
Medium Half-Life (<100 años)
Short Half-Life (< 30 dias)
High A actinides
Thermal and Fast Fission
Fast Fissión
Low Fission Cross Section
TRU Transmutation Scheme
238,241
242m
Fast Spectrum
Actinides with very short half life (10-200 yr):
Pu,
Am, 243,244Cm
Fast Spectrum Transmutation Scheme
Av. Flux Intensity (n/cm2/s)
3,00E+15
Second
Hour
Day
Year
1 Time Unit
3600 31570560
86400
3E+07
Cm242
Cm243
Cm244
Cm245
Cm246
a / SF
a / EC/ SF
a / SF
a / SF
a / SF
a
100 / 6.2E-6
9 9 . 7 / 0 . 2 9 / 5 . 3 E- 9
100 / 1.35E-4
100 / 6.1E-7
100 / 3E-2
100
0,446
29,068
18,080
8490,695
4724,813
18,130
2,798
6,257
2,922
16,459
64,7%
8,0%
65,2%
11,4%
44,6%
Am241
Am242
Am243
Am244
a / SF
b- / EC
IT / a / SF
a / SF
b- / EC
100 / 3.77E-10
82.7 / 17.3
9 9 . 5 / 0 . 4 6 / 1 E- 3
100 / 3.7E-9
100 / 4E-2
Am242m
432,225
0,002
140,846
7361,922
3,652
17,792
1,844
4,892
44% : 44%
13,1%
8,4%
87,0%
Pu239
Pu240
Pu241
Pu242
Pu243
a / SF
a / SF
a / SF
b- / a
a / SF
b-
100 / 1.9E-7
100 / 3.1E-10
100 / 5.7E-6
100 / 2.45E-3
100 / 5.5E-4
100
24083,608
6556,805
14,334
372891,707
0,001
4,220
3,477
9,033
2,688
11,354
6,775
37,5%
19,4%
54,8%
14,2%
61,1%
30,6%
Np237
Np238
Np239
a / SF
b-
b-
a / SF
100 / 2E-12
100
100
100 / 3.1E-10
2137656,095
0,006
4,332
15,928
81,5%
13,1%
0,006
15582935,494
0,001
Pu238
87,644
Cm247
Pu239
Ln(2)/(f)
24083,608
3,477
19,4%
Symbol & Mass
Decay modes
Branching ratios
Half-Life
Absorption-Half-Life
(n,g)/absoption
• These isotopes are key steps for the nuclear waste breeding, but their
radioactivity makes their measurement very difficult.
• Very low mass samples (<<1 mg): to reduce the radioactivity induced
background and to be compatible with R.P. rules.
• Same conditions allow very rare materials (even deposits from rad beams
ISOLDE?), and materials of very low cross section:
90Sr, 79Se, 126Sn, 147Pm, 135Cs: long lived FF
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
29
The next frontier: n_TOF @ EAR2
(1)
(2)
(3)
(4)
(5)
Radioactivity background
High brightness (peak flux intensity) and low duty cycle
Shorter flight path 1/10 -> 10-100 times larger flux (EAR2)
Scattered beam background
Very thin sample support no encapsulation
Class A laboratory (EAR2)
Distance from samples to walls (EAR2)
Background vs. Detectors
Low neutron sensitivity of detectors
Improved background rejection by detectors
In beam background
Large angle of neutron and proton lines (EAR2)
Optimized moderator
Ambient background
Walls distance and
detector background rejection
New
experimental
area at 20 m
n_TOF target
Experimental
area at 185 m
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
30
Summary and conclusions
• n_TOF @ CERN is a first class neutron Time Of Flight facility
• It is specially well suited for radioactive materials, samples of rare materials or
low cross section.
• Excellent facility for measuring neutron capture and fission cross sections and
the most needed cross sections identified for nuclear applications (nuclear
waste minimization). Sustained support from the EU framework programs.
• The measurements provide very relevant parameters to improve the
understanding and physics models of nuclides and reactions.
• Combined with high performance detectors and DAQ allows to perform high
accuracy cross section measurements.
• The n_TOF potentiality was proved by successful operation from 2000 to 2004
• The current campaign, with improved setup, will allow to fully exploit its
possibilities to fulfill the request of the highest priority nuclear data needs
• There are plans to enhance the performance with an additional short flight path
and EAR2 that will allow to open a new frontier of sample masses, short lived
isotopes and accurate measurements
E. Gonzalez: Nuclear data at n_TOF for fundamental science and industrial applications (AHIPA09 - Fermilab)
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